首页> 外文会议>12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors 2005 vol.1 >FRACTOGRAPHIC OBSERVATIONS ON A HIGHLY IRRADIATED AISI 304 STEEL AFTER CONSTANT LOAD TESTS IN SIMULATED PWR WATER AND ARGON AND AFTER SUPPLEMENTARY TENSILE AND IMPACT TESTS
【24h】

FRACTOGRAPHIC OBSERVATIONS ON A HIGHLY IRRADIATED AISI 304 STEEL AFTER CONSTANT LOAD TESTS IN SIMULATED PWR WATER AND ARGON AND AFTER SUPPLEMENTARY TENSILE AND IMPACT TESTS

机译:在模拟压水堆和氩气中进行恒定载荷试验后,对高辐照强度的AISI 304钢进行的断口形貌观察以及补充拉伸和冲击试验后的分形观察

获取原文
获取原文并翻译 | 示例

摘要

Intergranular cracking has been observed in highly irradiated AISI 304 following constant load tests at 340 ℃ in both simulated PWR water and, to a lesser extent, argon. Complementary investigations to clarify the mechanical behavior of the irradiated steel were performed. Those investigations consisted of tensile tests in air at room temperature and at 300 ℃, and impact testing in air at room and liquid nitrogen temperatures. The prevailing fracture mode for the irradiated material was ductile-dimple at 300 ℃ (using a strain rate of 1·10~(-3) s~(-1)) and intergranular at room temperature and below. The results of the investigations show that the irradiated stainless steel studied is susceptible to intergranular fracture without environmental assistance. The results are discussed based on the possible influences of strain rate, temperature and environment on the fracture mode in highly irradiated stainless steels.
机译:在模拟PWR水和较小程度的氩气中,在340℃进行恒定载荷试验后,在高度辐照的AISI 304中观察到晶间裂纹。进行了补充研究以阐明辐照钢的机械性能。这些研究包括在室温和300℃的空气中的拉伸试验,以及在室温和液氮温度下的空气中的冲击试验。辐照材料的主要断裂模式是300℃时的韧性凹痕(使用1·10〜(-3)s〜(-1)的应变速率),在室温及更低温度下为晶间。研究结果表明,所研究的辐照不锈钢在没有环境辅助的情况下很容易发生晶间断裂。基于应变率,温度和环境对高辐照度不锈钢的断裂模式的可能影响,讨论了结果。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号